ML17341B045
| ML17341B045 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 04/15/1982 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17341B044 | List: |
| References | |
| NUDOCS 8204260202 | |
| Download: ML17341B045 (98) | |
Text
reac'Aj'vity inser~upon ejection greater than O~k/k at rated power.Inoper ab rod worth shall'e determined
~nin 4 weeks.b.A control rod shall be considered inoperable if (a)the rod cannot be moved by CRDM, or (b)the rod is misaligned from its bank by more than 15 inches, or (c)the rod drop time is not met.c.If a control rod cannot be moved by the drive mechanism, shutdown margin shall be increased by boron addition to compensate for the withdrawn worth of the inoperable rod.5.CONTROL'ROD POSITION INDICATION If either the power range channel deviation alarm or the rod deviation monitor alarm is"not operable, rod positions shall be logged once per shift and after a 1'oad change greater than 105 of rated, power.If both alarms are inoperable for two hours or more, the nuclear overpower trip shall be reset to 93$of rated power.6.-POWER DISTRIBUTION LIMITS a.Hot channel factors: (1)F~Limi t The hot channel factors (defined in Bases)must meet the following limits at all times except during low power physics tests: Fg (Z)-(~Fg~L/P)x K(Z), for P>0.5 F~(Z)<(2 x fF~]L)x K(Z), for P<0.5 F<1.55 f1.0+0.2 (1-P)$>H Where P is the fraction of rated power at which the core is operating; K(Z)is the function given in Figure 3.2-3 or Figure 3.2-3a;Z is the core height location of F.[F~]L and K(Z)are dependent on the steam generator tube plug)ing level as follows: Plugging level>5 g, and<285<5$[F~]L Figure Number for'K(Z)2.125 3.2-3 2.30 3.2-3a (2)Augmented Survei l lance (MIDS)If$F~], as predicted by approved physics calculations, exceeds[Fq]L t3en the power will be limited to a turnon power fraction, PT, equal to the ratio of$F]L divided by fF~], or, for operation at power levels ab6ve.P7, augmented s(rveillance of hot channel factors shall be implemented, except in Base Load 3.2-3.4/15/82 4 M 4 b"'~'<<'b Ii i b M V t ith s~b'(,.>>4!I lf v 4 4 M'h r'4<>I C<<4>>~'!.'5~'Vt I ih I M M Mr 0 4,", lt,i M M I'r fl h.<<, 4 b'i'., b\f'r, r 4 i f 4 I rt M'I'~
HOT CHANNEL FACTOR NORMALIZED OPERATING ENVELOPE (for (5%steam.generator tube plugging and F=2.30)(6.0,1,.000)
(10.8,.939)(12.0,.43 10 CORE HEIGHT'FT.
)FIG.3.2-3a 4/15/82 Qi I I a!i.~~')C~fg III$T,>P F">>jl Cf i s, ('I Sa.ety Analysis for Turkey Point Unit 3, and 4 Loss-of-Coclant-Accident The.s<-of-c="l=-nt ac'c.dent ,LCC~)has b en rea".,alyzed for Turkey Point 3~'"~-"-~-~a~~":
..;o"'el<4F steam~e..e."ators and 5 percent steam gal:ei a o u=p J4ging inis a i'a~is iou IG a Iso Le appl cab i 2 to TU4ey Point Unit 4 (FLA)provided that it also has replaced model 44F steam generator.
The following report amends ihe section of ihe Safety Analysis Report on major reactcr coo'.ant system pipe ruptures (Chapter 14.3.2).Th analysis presented here is in accordance with the reouirements of 10CFR50.46, Appendix K provided in reference l.A description of the Westinghouse Emergency Core Cooling System (ECCS)Evaluation Model used for this analysis is presented in l!CAP-8839 (ref-erence 2)..The individual comouter codes which comprise the Westing-house ECC Evaluation Model are described in detail in references 3, 4, 5, and 6.The results of several sensitivity studies are reported in reference 8.These results are for conditions which are not limiting in nature-and hence are reported on a generic, basis.Since the initial development of the Appendix K ECCS Evaluation Model, several model changes were'ade, submitted to the NRC for review and approved for use in design LOCA analyses.These modifications are specified in references 7, 9, 10, 11, 12, 13, and 14.The LOCA analysis presented in this report utilized the: 1981 version of the evaluation model which is the model currently used and accepted for plant licensing calculations.
The modifications which comprise the 1981 evaluation model are delineated in reference 12.
I~I 0 i Resul ts The analysis of the loss-of-coolant accident is performed at 102 percent of the licensed core power rating.The peak linear power and total core power used in the analysis are given in Table 2.Since there.is margin between the value of peak linear power density used in this analysis and the value of the peak linear power density expected during plant operation, the peak clad temperature calculated in this analysis is greater than the maximum clad temperature expected to exist.Table 1'resents the occurrence time for various events throughout the accident transient.
Table 2 presents selected input values and results from the hot fuel rod thermal transient calculation.
For these results, the hot spot is defined as the location of maximum peak clad temperatures.
That 1'ocation is speci-fied in Table 2 for each break analyzed.The location is indicated in feet which is the elevation above the bottom of the active fuel stack.Table 3 present's a summary of the various containment systems parameters and structural parameters which were used as, input to the COCO computer code[6]used in this analysis.Tables 4 and 5 present reflood mass and energy releases to the containment, and the broken loop accumulator mass.and energy release to the containment, respectively.
Figures 1 through 17 present the transients for the principle parameters for the break sizes analyzed.The fol-lowing items are noted: Figures lA-38: Quality, mass velocity and clad heat transfer coef-ficient'for the hotspot and burst locations Figures 4A-6B: Core pressure, break flow, and core pressure drop-The break flow is the sum of the flowrates from both ends of the guillotine break.The core pressure drop is taken as the pressure just before the core inlet to the pressure just beyond the core outlet Figures 7A-9B: Clad temperature, fluid temperature and"core flow.The clad and fluid'temperatures are for the hot spot and burst location.Figures 10A-llB: Downcomer and core water level during reflood, and flooding rate Figures 12A-13B: Emergency core cooling system flowrates, for both accumulator and pumped safety injection Figures 14A-15B: Containment pressure and core power transient Figures 16, 17: Break energy release during blowdown and the con-tainment wall condensing heat transfer coefficient for the worst break 1635Q:1
~, I (4)Conc lusions-Thermal Analysis For break up to and including the double-ended severance of a reactor coolant pipe, the Emergency Core Cooling System will meet the Acceptance Criteria as presented in 10CFR50.46 That is: 1.The calculated peak.clad temperature does not exceed 2200 F based on a total core peaking factor of 2.30.2.The amount of fuel element cladding that reacts chemically with water or steam does not exceed 1 percent of the total amount of Zircaloy in the reactor.3.The clad temperature transient is terminated at a time when the core geometry is still amenable to cooling.The, cladding oxidation limits.of 17 percent are not exceeded during or after quenching.
The core temperature is reduced and decay heat is removed for an extended period of time, as required by the long-lived radioactivity r emai ning i n the c ore.1635Q: 1 ii (5)References 1."Acceptance Criteria for Emergency Core Cooling Systems for Light Mater Cooled Nuclear Power Reactors"', 10CFR50.46 and Appendix K of 10CFR50.46.
Federal Register, Volume 39, Number 2, January 4, 1974.2.Bordelon, F.N., Massie, H.M., and Zordan, T.A.,"Westinghouse ECCS Evaluation Model-Summary", WCAP-8339, July 1974.3.Bordelon, F.N., et al.,"SATAN-VI Program: Comprehensive Space-Time Oependent Analysis of Loss-of-Cool,ant", WCAP-8302 (Proprietary Version), MCAP-8306 (Non-Propietary Version), June 1974.4.Bordelon, F.M., et al.,"LOCTA-IV Program: Loss-of-Coolant Tran-sient Analysis", WCAP-8301 (Proprietary Version), WCAP-8305 (Non-Proprietary Version), June 1974.5.Kelly, R.0., et al.,"Calculational Model for Core Refloodi ng After a L'oss-of-Coolant.
Accident (WREFLOOD Code)".MCAP-8170 (Proprietary Version), MCAP-8171 (Non-Proprietary Version), June 1974.6.Bordelon, F.N., and Murphy E.T.,"Containment Pressure Analysis Code (COCO)", MCAP-8327 (Proprietary Version), MCAP-8326 (Non-Pro-prietary Version), June 1974.7.Bordelon, F.M., et al.,"The Westinghouse ECCS Evaluation Model: Supplementary Information", MCAP-8471 (Proprietary Version), WCAP-8472 (Non-Proprietary Version), January 1975.8.Salvatori, R.,"Mestinghouse ECCS-Plant Sensitivity Studies", MCAP-8340 (Proprietary Version), WCAP-8356 (Non-Proprietary Ver-sion), July 1974.9."Westinghouse ECCS Evaluation Model, October, 1975 Versions," MCAP-8622 (Proprietary Version), MCAP-8623 (Non-Proprietary Version), November 1975.1635(}: 1 I'-l*
10.Letter from C.Eicheldinger of Westinghouse Electric Corporation to D~8~Yassalo of the Nuclear Regulatory Commission, letter number NS-CE-924, January 23,, 1976.11.Kelly, R.D., Thompson, C.M., et al.,"Mestinghouse Emergency Core Cooling System Evaluation tlodel for Analyzing Large LOCA's During Operation With One Loop Out of Service for Plants Without Loop iso-lation Valves", WCAP-9166, February 1978.12.Eicheldinger C.,"Westinghouse ECCS Evaluation Model, 1981 Version", WCAP-9220-P-A (Proprietary Version), MCAP-9221-A (Non-Proprietary Version), Revision 1, December 1981.13.Letter from T.A.Anderson of Westinghouse Electric Corporation to John Stolz of the Nuclear Regulatory Commission,~letter number NS-TMA-1981, November 1, 1978.14-Letter from T.A.Anderson of Westinghouse Electric Corporation to R.L.Tedesco of the Nuclear Regulatory Commission, letter number NS-TtQ-2014, December ll, 1978.1635():1
~i TABLE 1 LARGE BREAK TINE SEQUENCE OF EVENTS DECL Cp=(Sec)DECL C=0.6 p (Sec)START Rx Trip Signal S.I.Signal Acc.Injection End of Blowdown Bottom of Core Recovery Acc.Empty Pump Injection End of Bypass 0.0 0.72 1.13 14.7 32.93 54.44 62.79 25.74 32.93 0.0 0.71 0.60 11,3 28.14 49.00 57.83 25.60 28.14 TABLE 2 LARGE BREAK DECLG C=0.4 D DECLG C=0 6 D Res ul ts Peak Clad Temp.F Peak Clad Location Ft.Local Zr/H20 Rxn (max)$Local Zr/H20 Location Ft.Total Zr/H20 Rxn X Hot Rod Burst Time sec Hot Rod Burst Location Ft.2195 7,25 6.07 7.25<0.3 45.2 5.75 2053 6.75 3,968 7.5 0,3 45.0 6.0 Ca 1 cul a ti on NSSS Power that 102K of Peak Linear Power kw/ft 102%of Peaking Factor (At License Rating)Accumulator Water Yolume (I'~<<~-'~<<'~~~~2200 13.07 2.30 875 ft Fuel.region+cycle analyzed uHZTI3 UNIT~4)(If applicable)
Cycl e Region Al 1 Al 1
<Qi TABLE 3 (Page 1 of 3)CONTAINMENT OATA (DRY CONTAINMENT)
Net Free Volume 1.55 x 106 Ft3 Initial Conditions Pressure Temperature RMST Temperature Service Mater Temperature 14-7 psia 90.0'F 39.0 F 63.0 F Spray System Number of Pumps Operating Runout Flow Rate Actuation Time 2.l450 gpm sec.Safeguards Fan Coolers Number of.Fan Coolers Operating Fastest Post Accident Initiation of Fan Coolers 26 secs.
Qi~,
TABLE 3 (Page 2 of 3)STRUCTURAL HEAT SINK DATA'Materi al Thickness'(in)Area (Ft)Paint Carbon Steel 0.006996 0.2898 87335.8 Carbon Steel 0.006996 1000086.0 Paint Carbon Steel 0.006996 0.4896 35660.11 Carbon Steel 0.4896 12367.5 Paint Carbon Steel Concrete 0.006996 0.2898 24.0 50430.0 Carbon Steel Concrete 0.2898 24.0 16810.0 Paint Carbon Steel 0.006996 1.56 4622.69 Carbon Steel 1.56 1540.89 Paint Carbon Steel 0.006996 5.496 1277.87 Carbon Steel 5.496 425.93 Paint Carbon Steel 0.006996 2.748 951.525 0',~
TABLE 3 (Page 3 of 3)STRUCTURAL HEAT SINK DATA Wall Material Thickness (in)Area (Ft)12 Carbon Steel 2.748 317.175 13 Paint 0.006996 Carbon Steel'.03 23550.0 Paint Carbon Steel 0.006996 0.063 80368.5 15 Paint Carbon Steel 0.006996 0.10 42278.25 16 Carbon Steel.0.2898.17190.0 17 Stainless Steel 0.032 113253.4 18 Stainless Steel 2.1264 3704.0 19 20 Stainless Steel Concrete Concrete 0.1398 24.0 24.0 14392.0 59132.0 i5 I I TABLE 4 REFLOOD MASS AND ENERGY RELEASES: Time ('sec)DECLG CD-0.4"Total (ibm/sec)0 Total (Btu/sec)54.347 55.669 0.028 35.68 62.891 19.48 25135 74.291 32.84 42383 92.191 111.591 45.47 62.32 57824 78159 130.791~75.63 94204 149.791 87.12 108032 186.891 285.03 161152 226.791 298.71 152313 271.091 312.18 141932 321.491 328.83 130016 382.191 342.69 115551 eoI n~
'(Qi l TABLE 4B REFLOOD tlASS.AHD~ihERGY RELEASES DECLG CD=0.6 Time (sec)iOTAL (ibm/sec)TOTAL (.BTU/Sec 49,.001 49,826 57.410 68.529 85.929 104.929 124.029 142.929'79.929 219.329 263.229 313.329 373.829,0.03 33.17 34.49 50.14 65.35 77.64 88.47 274.99 291.11 304.64 321.21 341.73 0 35.2 42713 44423 63315 81692 96478 109506 162328 154284'43981 132490 1'17812' 9F Oi Qi~I Table 5 II DECLG CD=0.4 Broken Loop Injection Spill During Blowdown T IHE 0.000 1.010 2.010 3.010'4.010 5.010 6.010 7.010 8.010 9.010 10.010 11.010 12.010 13.010 14.010 HASS 3083.402 2775.985 2549.479 2371.235 2225'.996 2104.580 2000.289 1909.287 1828.531 1756.087 1690.537 1630.928 1576.546 1526.743 1480.928 ENERGY 183832.451 165504.238 151999.952 141373.054 1327'13.868 125475.082 119257.219 113831.700 109016.989 10I697.907 100789.842 97235.939 93993.651 91024.431 88292.925 ENTHALPY 59.620'59.620'9.620 59.'620 59.620 59.620 59.620 59.620 59.620 59.620 59.620 59.620 59.620 59.620 59.620 1 5.010 16.010 17.010 18.010 19.010 20.010 21.010 22.010 23.010 24.010 25.010 26.010 27.010'8.010 29.010 30.010 31.010 32.010 1438.640 1399.477 1363.118 1329.230 1297.278 1267.106 1238.699 1212.124 1187.431 1164.479 1142.940 1122.957 1104.421 1086.744 1070.187 1054.268 1039.041 1024.474 85771.693 83436.827 81269.116 79248.708 77343.735 75544.886 73851.229 72266.830?0794.611 69426.222 68142.087 66950.723 65845.604 64 791.649 63804.549 62855.469 6194?.622 61079.153 59.620 59.620 59.620 59.620 59.620 59.620 59.620 59.620 59.620 59.620 59.620 59.620 59.620 59.620 59.620 59.620 59.620 59.620
$l C I, I I Tabi e 5 8 DECLG CD=0.6 Broken Loop Inje Cion Spii)Ourina Biolvciolsn T lP P M~4.010 S.O10 6.010 7.010 8.010 9.010'I 0.010~1.010 12.010 13.010 1~.010'4o J}4 0'M~I I~2544.223 23cv~~mt 2217.".": 2094.SQ2'l988.200 1895.206 1812.9O7 I7o9~0~3 1673'02 16'<47 1S59 682 1466.596l.~I(CRI V~~8"0'o~)~ol i i~ilier,/~J~aL J~~124874.218 118536.465 1"i2992.2Q9 108085.507 99756'74 961.9.686 929o8.245 a7438.'469 TPA'a+~os.3)~J 59.<23 59.620 0>~6m.V c,o 4's V 594 620 59.':0 5).620 1 5.010 16.010 17.010 18.010 19.010 20 010 21.019 22.010 23.010 24.010 25.010 26.010'7.010 1425.293 1386.597 1350.,397 131?.382 1286.947 1258.891 1233.052 1208,918 1186.570 1165.640 1145.727'I126.662 1108.630 84975.953 82668.919 80510.683 78542.306 7.6222 7b>>75055,089>>
73514.588 72075.697 70743'21 69495,43Q 68308.260 67171.562 66096.497 59.620 59.620 59.620 59.620 59.620'9.620 59.620 S9.520 59.520 59.620 59.620 59.620 59.620 0 0 1)O~
I.anno 1.2500 FPL IBBI ECCS HOOEL O.a OECLC F0=2.30 REPLACEO STEAH GENERATOR OUALITY OF FLUIO BURSTS 5.15 FTI)PEAKED 7.25 FTli)I 1.0000 0.7500 0.Sfjnn 0.2500 0.0 Cl 0 Cl Cl 0 m Cl 0 0 00000 O O O OOOO O 0 O OOOO EJ lh CQClo~~~~~~~0 0 OOOO>>0 0 0 D 0 O O 0~~hl m 0 0 O O O 0 0~~O OOOO 0 oooo 0 OOOO 0 OOQ~~~~g h gglw 0 0 0 Cl 0 O O OOOOO 0 O QOQQQ 0 0 OQQQ~~~~~~0 0 OOOQQ e ill e r lllCn>>Cl m 0 0 0 0 O 0~~~O O 0 0 0 Vl sD O OOO QQQ~n o~w D QOQ w Q)71m TINE ISECi' i I l.F000 1.2500 FPL 1981 ECCS HOOEL 0.6 OECLG FOD2.30 REPLACEO STEAH GENERATOR OUALlfY OF FLU10 QUR5>, 6.00 Ff{>PE'AK.6.15 Ffl~)1.0000~0.~500 0.5000 0.2500 0.0 CD ,Cl CI CD CI IA O 0 OOOO 0 0 O OOOO 0 0 O OOOO ifl CCI N COCIIO~~~~~~~0 O OOOO>>CD Cl Cl CD Ill 0 CD CI 0 0 00000 0 0 D DODO O 0 OOOOO 0 0 OOOO~~~~~~eO Vl CO>COOl>>TIHE (SEC)CI CI CD m 0 0 00000 0 0 00000 0 0 OOOO~~~~~~tn 0 0 000OO r e@II OOI 0 0 Cl m O OOOO 0 0 0 neo~~~O 0 OCICI 0 0 nonon
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Q>e ig)0 STATE OF FLORIDA))COMTY OF DADE)ss~Robert E.Uhrig being first duly sworn, deposes and says: That he is Vice President Light Company, the herein;of Florida Power That he has executed the foregoing document;that the state-ments made in this said document.are true and correct to the best of his knowledge, information, and belief, and that he is authorized to execute the document on behalf of said Robert E.Uhrig Subscribed and sworn to before me this~5.dav of 4'GTARY'.PvUBLIC, n and for the County of Dade, State cf Flori a Notary Public, State of Rorida at Large My COmmiSSiOn eXpireS,'Exing~October 30, 1983 Bonded thru Maynard Bonding Agency 0 l i~%W